ML20040H136

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Monthly Operating Repts for Jan 1982
ML20040H136
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/01/1982
From: Beth Brown, Weinfurter E
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20040H130 List:
References
NUDOCS 8202170246
Download: ML20040H136 (25)
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Text

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  • QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERPORMANCE REPORT JANUARY 1982 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS CAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8202170246 820201 PDR ADOCK 05000254 R PDR

T n a . .

TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant of Procedure 9hanges, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions .

VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary L

l

I. INTRODUCTION Quad-Cities Nuclear Power Station is composed oE two Boiling Water Reactors,' each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, Illinois. The Station is jointly owned .

, by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.. The Nuclear Steam Supply Systems are General Electric

  • I C spany Boili'ng Water Reactors. the Architect / Engineer.was .

Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The condenser cooling method is a closed cycle spray canal, and the Mississip'pi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket Numbers ,50-254 e

and 50-265. The date of initial reactor critica11 ties for Units 1 i

and 2 respectively'were October 18, 1971, and April 26, 1972.

Canmercial generation of power began on February 18, 1973 for Unit 1 and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Erich Weinfurter, telephone number 309-654-2241, extensions 127 and 194.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE January I-8: Unit One started the reporting period holding load at 819 MWe. On January 3 it dropped load to 675 MWe to do weekly Turbine tests and reverse condenser flow. Subsequently, load was returned to 818 MWe.

On January 5 load was decreased 25 MWe to change condensate booster pumps and subsequently returned to maximum attainable load.

January 9-17: At 0015 on January 9, load was reduced to 600 MWe to do the weekly Turbine tests. Load was then increased to 813 MWe.

January 17-26: At 0100, January 17, the load was dropped to 700 MWe to do weekly Turbine testing. At 0300, load was increased to maximum attainable load. On January 23, at 0045, load was dropped to 600 MWe to perform weekly Turbine testing, reverse condenser flow, and adjust the control rod pattern. At 0300, load was increased at 5 MWe/ hour.

On January 25, at 0335, the load increase was terminated due to reaching the maximum flow control line. At 0815, load was increased to 813 MWe.

January 27-31: At 1338, January 27, Unit One scrammed on a spurious signal to both Reactor Protection System channels "A" and "B". By 1858, the Reactor was critical, and the Unit was back on line ,t 2145 and increasing load to 400 MWe in 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The load increase was stopped at 550 MWe, at 0430, on January 28 to inspect the RCIC System. At 0445, load was increased at 8 MWe/ hour until at 0750 on January 29 Then the Unit increased load 25 MWe/ hour. At 0930, the load increase continued at 5 MWe/ hour to maximum attainable load. At 0100, January 31, Unit One load was dropped to 700 MWe to do weekly Turbine testing. At 0300 load was returned to 817 MWe.

B. UNIT TWO January 1-4: Unit Two started the reporting period derated to a maximum l output of 380 MWe due to the "B" Recirculation Motor-Generator Set being l out of sequence. At 0515, on January 3, the "B" Feedwater valve went closed as a breaker was being reset. The Reactor scrammed on low water i level. The Reactor was critical by 1240 and was on line at 2115, and lead was then held at 378 MWe, 1

l January 5-12: On January 5, at 1235, the "B" Recirculation Motor-Generator Set was returned to service; after starting the 2B Recircu-lation pump, load was increased to 710 MWe. At this level condensate demineralizer problems restricted load and the unit load had to be dropped to 500 MWe. On January 8, load was increased to 625 MWe. At 1600, on January 9, load was increased to 823 MWe which was reached at 0600, January 11.

F II.

SUMMARY

OF OPERATING EXPERIENCE (Continued)

January 13-14: January 13, at 0300, load was reduced to 770 MWe to make control rod pattern changes. Load was then increased to 809 MWe. At 2000, load was dropped to 750 MWe due to condensate demineralizer '

problems.

On January 14, load was reduced to 600 MWe due to condensate demineralizer problems. By 1230 a load increase to maximum attainable load was begun. At 2155, "B" Recirculation Motor-Generator Set was shut down when the exciter started to spark. Load was dropped to 357 MWe.

January 15-31: At 1105, January 15, during a Drywell entry to check the oil level in 2B Recirculation pump, a small crack was found in the Reactor Water Clean-up suction piping. The Unit was shut down by 1330 and will be down until repairs are completed, around the end of February.

c III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications On December 23, 1981, the NRC issued Amendment 69 to license DPR-30. This amendment provided changes to the license and Technical Specifications required to operate Unit Two with the fuel load for cycle 6. Unit Two began operating in cycle 6 on Dec. ember 26, 1981.

B. Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure Changes requiring NRC approval for the reporting period.

C. Tests and Experiments Requiring NRC Approval There were no Tests and Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q15517 Diesel Air Start Worn head gasket 1/2 & Unit 2 Diesel Replaced head gasket Compressor 6601 & valve gasket operable & valve gasket Q15829 Suppression Repair thermocouple installed original-

. Chamber Water thermocouple &

Temperature wired Recorder 1-160-2-8 Ql6072 Diesel Generator Lube oil leak Unit 2 Diesel Tightened bolts on found in cooler operable cover of tube oil cooler Q15375 HPCI High Pressure Leaking oil Repaired during Replaced gasket oil Pump Outboard Oil weekend outage piping Seal 1-2302 (11-6-81)

Q17083 82-1/03L Yarway LIS-1-263- Loose shaft on The other three Epoxied shaft flange 72A switch assembly switches in the & assembled switches system were operable and indicator Q17589 RCIC Turbine isolates for no None--still was Replaced micro-1-1360-IA & IB reason working--no leakage switches & recalibrated f

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q7174 Torus Vacuum Limit switch needs It was demonstrated Re-adjusted 1imit Breaker 2-1601-33E adjusted the vacuum breaker switch would open, so safe

~

operation is o.k.

Q14693 inboard Main Steam Seal ring & packing Valve failed the Local Replaced seal ring &

Line Drain M0 are bad Leak Rate Test packing

- 220-1 Q14721 Inboard "B" Feed- Seal ring & 0-ring Valve failed the Local Replaced seal ring &

water Check Valve worn Leak Rate Test 0-ring on seat 2-220-588 Ql4726 RHR Torus Spray Lock nut loose Valve failed the Local Weld lock nut to disc 2-1001-36A Leak Rate Test collar on stem Q14729 Outboard "B" Feed- Worn 0-ring Valve failed the Local Repaired 0-ring &.

water Check Valve Leak Rate Test re-assembled valve 2-220-62B Q14530 RCIC Steam Supply Worn seal ring Valve failed the Local Repacked seal ring &

Valve M0-2-1301- Leak Rate Test replaced stem; disc 17 o.k.

QI4402 Reactor Head Vent Leaking diaphragm Leaking air through Replaced diaphragm 2-220-47 diaphragm & tested Q13850 2-2301-15 Motor grounded Only alarmed when Replaced motor &

valve is exercised tested valve I

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

. W.R. LER OF ON ACTION TAKEN T0.

NUMBER NUMBER COMPONENT MALFUNCTION SAFE LPERATION PREVENT REPETITION I'

' ~

Q13328 RCIC Flow Con- Limit pot hoods Vill not maintain 400 Adjusted hi limit I troller FIC 2- adjusted gpm at 1250 psi in pot; recalibrated 1340-1 AUTO. In manual o.k.

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Q12384 81-9/03L RHR Suppression Worn shaft bearing liigher than nornal Replaced worn shaft i Chamber Dump current when open bearing; clean valve Line 2-1001-37B closed Q11042 Diesel Generator Keep losing level The Diesel was still Plugged one tube..on Heat Exchanger on Unit 2 Diesel operable. heat exchanger;

, 6601 Generator cooling re-installed coolers water Q14942 81-19/03L-l' RHR Service Seal needs adjusted Penetrations failed Adjusted seals &

Water Vault the Local Leak Rate caulked Penetrations Test

, Q14963 81-20/03L-1 Drywell Purge Packing needs Drywell Purge failed Adjusted packing at isolation A0- adjusted Local Leak Rate Test end opposite valve '

2-1601-21 operator i

Q16137 81-18/03L Torus Spray Rebuild & re-weld Valve failed Local Rebuilt & re-welded i l Bypass 2-1001-368 bushing Leak Rate Test bushing & re-lapped.

valve Q14712 Service Water Pinhole leak in .The pump.was still Drilled & tapped 2C RHR 2-1001-65C pump casing operable pinhole Icak;

installed 1/3 inch pipe plug i

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q12930 2D RHR Service Coolin3 water line The pump was still Repaired leak on Water Pump 2-1001- leaking operable inboard cooling 65D water line

, Q16430 "HR Heat Exchanger Worn torque switch

. Operable, but needs Replaced torque switch Bypass 2-1001-16A in the valve to be replaced ope rator Q16456 Pressure Check valve will not Cold shutdown ISI Cleaned & inspected Suppression System operate testing check valve; works o.k.

Check Valve 2-220-81E Q16457 Pressure Check valve will not Cold shutdown ISI Cleaned & inspected Suppression System operate testing check valve; works o.k.

Check Valve 2-220-81B Q16542 Excessive Flow Inspected check Failed test. ST 47, Removed valve & checked I Check Valve 2-263- valve; not working the check valve for proper operation 2-15A properly operability Q16558 595-123 PCI The relay coil A Group til isolation Replaced the relay was burnt occurred in the & tested safety mode Q16575 Main Steam Drain Dirt was found in Failed Local Leak Rate Cleaned & inspected M0-2-220-1 the seating area Test < talve Q16587 inboard Main Loose seat Failed Local Leak Rate Adjusted the torque Steam Line 2-220-1 Test switch so seat would be tighter e

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATlON PREVENT REPETITION Q15277 24/48 VDC Battery The plates in cell The cell failed during The cell was replaced 2-8325 #2 were degraded the battery discharge & the discharge test test was performed

. Q15275 24/48 VDC Battery The plates in cell The cell failed during The cell was replaced 3 2-8325 #4 were degraded the battery discharge & the discharge test was performed test Ql5276 24/48 VDC Battery The plates in cell The cell failed during The cell was replaced 2-8325 #5 were degraded the battery discharge & the discharge test test was performed.

Q16603 Valve 2-1601-57 Bad torque switch Valve doesn't close Replaced torque switch N2 Make-up in the valve from Control Room & tested ope ra to r Q16661 Drywell Equipment Bad operator; the Valve does not open Installed new operator Drain Valve 2- piston seals were with control switch 2001-16 worn Q16692 CRD Accumulator Worn packing & worn Accumulator loses Repacked with new 22-77 0-rings pressure packing & installed new 0-ring Q16842 Steam Line Rad Needs calibration Surveillance test Calibrated 2D Main Monitor Steam Line Monitor Q09092 2B Recirc Pump Gasket leaking. The valve had a small Repalced lock nut Suction Valve between the body leak. Leakage was gasket & stem

& bonnet monitored in the Drywell sumps O

e

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT . MALFUNCTION SAFE OPERATION PREVENT REPETITION Q16273 2A2 24V Battery The plates in cell The cell failed during' installed new cell &

Cell #3 #3 were degraded battery discharge test performed discharge test.

. Q16274 2Al 24V Battery The plates in cell The cell failed during Installed new cell &,

Cell #8 #8 were degraded battery discharge test performed di:scharge test Q16275 2Al 24V Battery The plates in cell The cell failed during Installed new cell &

Cell #9 #9 were degraded. battery discharge test performed d;scharge test-Q16276 2Al 24V Battery The plates in cell The cell failed during Installed new cell &

Cell #11 #11 were degraded battery discharge test performed discharge test Q12930 2D RHR Service Pump leak on The pump was still Repaired leak on Water Pump 2- inboard cooling operable inboard cooling water 1001-65D water line line Q16659 HPCI Steam Line Bad valve will be Valve will not close Replaced valve Drain Valve 2- repaired under from Control Room.

2301-29 Work Request Q17321

r IV . LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 82-1/03L l-13-82 ECCS Yarway inoperable UNIT TWO 82-1/0lT l-15-82 Reactor Water Clean-up Line crack (in Drywell) 82-2/0lT l-26-82 Main Steam Line Low Pressure Switch--Set-point Drift

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V. DATA TABUIATIONS i '

. The following data tabulations are presented in this report:'

A. Operating Data Report i

I B. Average Daily Unit Power Level

.j C. Unit Shutdowns and Power Reductions

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OPERATING DATA REPORT

.--..9 g

UNIT ONE DATEFebruarv 04 1982'

' ~ ~ ~ ~~ ~ ~

~~ COMPLETED BYErich Weinfortir~~~~

TELEPHONE 309-654-2241xi94 _ _ _ _ _

OPERATING STATUS

'~~

0000 010182 ~~ ~~'-

Reporting periodi2400'013182^Grosihours in r efoFtln~g p e r i od

~ ~

1. ~~744 ~
2. Currently authorized power level (MWt): 2511 Max. Depend capacity ~ ~ ' ~ ~ ~ ' ~ ~ ~ ~ ~

.(MWe-Net): 769* Design ~electrico1 rating '(MWeiNet):~~ 789 "

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s

_ 3.. Power level t o which restricted (if any)(MWe- _ Net ): NA __ _ _ _ . _ . _ _ . , _ _

4. Reasons for restriction (if any):

. _ . . _ _ - . _ _ - - . _ - - _ _ . . ~ . ._

5. Number of_ hours reactor _was critical _ 738.7 _ 738.7 69837.8 _
6. Reactor reserve shutdown hours 0.0 0.0 -3421.9

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7. ' Hours generator' on 1'ine ~~~ 735.9~ ~ ~ ~ ~ 735.9'~ -'6686774'~ ~

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. 8.. Unit reserve shu_tdown_ hours. . . _ . 0.0_ 0.0 909.2_ __

9. Gross thernal energy generated (MWH) 1743343 1743343 136801702

~

Gross electricol energf~'g~eneFrifed(MWH)~~

~

10'. 5756'42" ~~5756'42~ ~ ~44104575~ ~ ~

Li._ Net _electricci energy generated (MWH) . _ 536439 -536439 41120523

12. Reactor service factor 99.3 99.3 81.9

~B5.9 ~~

99.'3 13.' Reactor availab'111ty factor ~~ 99.3'

14. . Unit _ service factor. __ . _ .

98.9_ 98.9 78.4

15. Unit avo11obility factor 98.9 98.9 79.5

~ 93'8 ' ~ 62.7' ~~'

~

93.8'

~ '~

16. Unit copocity factor (Using MDC)
17. Unit _ capacity.. factor (Using Des.MWe) 91.4 91.4' 61.1
18. Unit forced outage rate i.i 1.1 7.1
19. Shutdowns sche'duled'over next 6 nonths (Type,Date,ond Duration of each):
20. If. shutdown _ot end of report __ period,estinated date_of stortup.___ M________.

$The M9C not be twer then 769 mit dsring periods of high onbient tenperatore due to the thernal perfernance of the sprey cenel.

OPERATING DATA REPORT DOCKET NO. 50-265

_. _ _ .____. __._ _ _ _ ___ _ ._._ _ . _ . . _ _ _ _ . . .__ .._ UNIT TWO __ _

DATEFebruarv 04 1982

~~ ~ ~~ ~ ~

' COMPLETED BYErich"Weinfurter~ ' ~

- _ _ . . _ _ _ _ _ , _ _ . . . . _. TELEPHONE 309-654-2241x194 _ _ _ _ _ _ _ _

OPERATING STATUS

~~0000 010182

1. Reporting periodi2400 013182 Gross hours ~1n reporting per1od!" '744 -

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2. Currently authori_ zed power _ level _(MWt): 2511_Hox. Depend copacity _ _ _ __ _ _ _ _

(MWe-Net): 769* Design electrical rating (MWe-Net): _ 789 3._ Power level to_which restricted (if__ony)(M_We-Net): NA __ __ __ _ _ _ _ _

4. Reasons for restriction (if .ny):
5. Number _of hours reactor was crit _ical 342.1 342.1 65193.9 _
6. Reactor reserve shutdown hours 0 ._0 0.0 2985.8

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336.5'~~ ~62577.7 ~~

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7. Hours gener o't or~~on 1ine

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336.5~

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8. Unit reserve shutdown hours. 0.0 0.0 702.9 9 Gross thernal energy generated (HWH) 619093 619093 128506176
10. Gross eiectrical ener'gy generoted('HWH)" ~ ~ ' ~196377' ~~196377~

~ ~ ~~

~409026'i7~ ~~~

ii. Het electrical energy._genero_ted(MWH) 183410 183410 39307994__ _

L2. Reactor service factor 46.0 46,0 77.3 13.' Reactor avo11obility factor ~

~~ 4 6'. 0 ~ ~ 46X ~~80.8

14. . Unit service factor _ 45.2 45.2 74.2 . _ .
15. Unit avo11ob111ty factor 45.2 45.2 75.0

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L 6'. Unit copoclty factor (Using MDC) ~32.i ~~ 32,i~~ ~ 59 d ~ ~

17. Unit.copacity factor (Using Des.MWe) 31.2 31.2 57.6
18. Unit forced outage rate 54.8 54.8 8.9
19. Shutdowns scheduled over next 6'nonths (Type ,Date ,and Duration o f ioch ) s

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20.. If shutdo.wn at end of report period, estimated. dote o f s tar t up_ J.gb_LL_HS;L__

8The IOC nef be lower then 769 leie dering periods of high onbient tenperatore det to the thersel perfernance of the sprey cenel, s

pp AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254

__ _ .. . _ _ _ ~~ '~~

. UNIT ~

~ 'ONE DATEFebruarv 04 1982 l

l COMPLETED BYErich Weinfurter l

'~

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~ ~ ~ ~ TELEPHONE 309-654-2241x194 HONTH Januorv 1982 _ _ . . _ _ _ _ __

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) _ ._ _ _ __.

(HWe-Net) _

i. 764.9 17. 744.7

'771'.4~

~

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2. 763.4
3. 724.6 19. 759,4 4, 752.8 20. 747.3

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5. ~ 756.2~ ~ 21. ~ 738.5
6. 761.7 22. 740.2
7. __

759.3 23. _

571.7

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8. ~ 755.7 24. ~679.4~~
9. 657,2 _ _ _ 25_. 745.O 10, 725.1 26. 763.8

~~

11, 774.4 ~~ ' 27.~ 439.5 .

12. 750.6 28. 509.0 _ _
13. 757.3 29. 680.9

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14. ~ 757.1 30,,. ~'742.5 15, 763.5 _ _

31, 735.6 _ _ . . _ _

16, 759.0

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INSTRUCTIONS ~

On this forn, list the overage daily init power level in Illie-liet for each det in the reporting nenth.Conpete to the nearest whole ne ouett.

f553 fineWa le!t c1ea f1 1

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ter the restrftted povef feveIb!fnsecbeses,c1kNstke overage!

e hef snit f power $sthet beet sh!vfl 5 e feetnoted to explain the apyarent onenely i

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. - ~ . - _ - - . pp AVERAGE DAILY UNIT PDWER LEVEL DOCKET NO. 50-265

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' UNIT' 'TWO DATEFebroorv 04 1982 COMPLETED BYErich Weinfurter

~ ~~ ~ ~ ~ ~ ~ ~ ~ ~

~ TELEPHONE 309-654-2241xi94 HONTH Januarv 1982 ._ ,_ _ _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) _ .

(HWe-Net) ._. _ _ _ _

i. 358.3 17. -10.9

'361.5

~~~~ ~~~

-10.8~

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2. ~ 18.
3. 142.6 19. -10.8
4. 349.8 20. -10.5
6. 627.0 . _ .______22._ -10.3 ._ _ _
7. 628.9 23. -10.3

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"24. -10.2 ~

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8' , 550.i

9. 619.9 __ _ _ _ _ _ _
25. -in,3 10, 677.6 26. -10.1

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Li. 787 .~ 0 ' ' 27. ~ 8,5

12. 757.3 28. -8.6 ___
13. 748.8 29. -8,5

~ ~ ~ ~ ~ ~ ~ ~~

14. ^ 596'.4~ 30. -

8.7 L5. 168.5 ._

31. -8.6 _
16. -11.0

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INSTRUCTIONS On this forn, list the everage daily unit power level in Mile-tiet for each day in the reporting nenth.Ceapete to the nearest whole ne uitt.

useU 1H1 fine Fer$el N' tfcele restrfcted povef t !e[ he vel '

l$)tdn eis sxUesesl,E yNkN" average SoIr e5 init power be lstlvEtet shN

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feetnoted to explain the apperent onenely

M M M f"! M M M M M M M M M F} .""1 i s 6 ..

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APPENDIX D QTP 300-S13 50-254 UNIT SHUTDOWNS AND POWER REDUCTIONS Revisici 5 DOCKET NO. March 1978 UNIT NAME Quad-Cities Unit One COMPLETED BY E. Weinfurter 309-654-2241, DATE February 1, 1982 REPORT MONTH TELEPHONE ext. 194 JANUARY 1982 o

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  • LICENSEE gg gg Co DURATION $ jr 3{ $ EVENT yo g:o u- " 2
  • o NO. DATE (HOURS) y! 5 3 REPORT NO. CORRECTIVE ACTIONS / COMMENTS R

82-1 820109 0,0 B 5 RB CONROD Reduced load for weekly Turbine tests and to change control rod pattern l 82-2 820123 0.0 B 5 RB CONROD Reduced load for weekly Turbine tests and to l change control rod pattern ]

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82-3 820127 8.1 H 3 lA ZZZZZZ Reactor scram on spurious scram signal l (final)

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M P M f"""! M F"" M M F""3 M M M C"") F"! ."'I T7 (~~

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  • APPENDIX D QTP 300-S13 50-265 UNIT SHUTDOWNS AND POWER REDUCTIONS Revisico 5 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit Two COMPLETED BY E. Weinfurter DATE February 1, 1982 309-654-2241, REPCRT MONTH TELEPHONE JANUARY 1982 ext. 194 o

a 5 s m z Et x 5 Ee S @ LICENSEE gg gg g DURATION $  %{$*

3 EVENT *8 g3 NO. DATE (HOURS) E ygg REPORT NO.

  • 8 CORRECTIVE ACTIONS / COMMENTS R

4 82-1 820103 F 12 75 A 3 CH VALVEX Reactor scram on low water level due to the "B"

, Feedwater Regulation Valve failing closed 82-2 820114 0.0 A 5 CB GENERA "B" Recirculation Motor-Generator Set shut down due to exciter sparking 82-3 820115 F 394.75 A 2 CG PlPEXX Unit shutdown to repair crack in Reactor Water Clean up line (final)

O

VI. UNIQUE REPORTING REQUIRINENTS The following items are included in _ this report based on prior commitments to the cammission:

A. Main Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram Timing Data for Units One and Two There were no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

i e

f VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandtsu l .(78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, t

Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

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QTP 300-S32 s~ ," "'

Revision 1 l

QUAD-CITIES REFUELING 'Harch 1978 6 , INFORMATION REQUEST u" 1. Unit: 1 Reload: 6 Cycle: 7 n 2. Scheduled date for next refueling shutdown: Sept 12, 1982 L  :

Dec 4, 1982 -

3 Scheduled date for restart following refueling:

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

p YES 5 Scheduled date(s) for submitting proposed IIcensing action and supporting C . Information:

- JULY 26, 1982 1,

l* 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis n [,, methods, significant changes in fuel design, new operating procedures:

{~I..I 7,

. litPLEftENTATION OF THE ODYN TRANSIENT ANALYSIS CODE AND RESULTS l (ftCPR SCRAM TIME DEPENDENCE) -

[,

J q .

l '

F 5-7 The number of fuel assemblies.

l

[ a. Number of assemblies in core: 224 new/724 total a- after the l b. Number of assemblies in spent fuel pool: outage 1940 o

[ 8. The present licensed spent fuel pool storage capacity and the size of any l

Increase in licensed storage capacity that has been requested or is planned n in number of fuel assemblies: .

a. Licensed storage capacity for spent fuel: 2920
b. Planned increase in IIcensed storage: 4636 new/7556 total

'~~

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

P- LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/34 v LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86

  • 'PPROVED A

1- APR 2.01978

,, Q.C.O.S.R.

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  • QTP 300-S32 n '

Revision 1

,-, QUAD-CITIES REFUELING *Harch 1978 6 , ( INFORMATION REQUEST b~~' 1. Unit: 2 Reload: 6 Cycle: 7 e7 2. Scheduled date for next refueling shutdown: Feb 27, 1983

' ~':  :

3 Scheduled date for restart following refueling: April 23, 1983 -

e,

{ 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

m NO J

5. Scheduled date(s) for submitting proposed IIcensing action and supporting

. Information:

u 'NONE i,

6. Important licensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis r, /. methods, significant changes in fuel design, new operating procedures:

L:? !, NONE 4%

d W,

q-2 .

i ,.e l'

" 7 The number of fuel assemblies. -

l

a. Number of assemblies in core: 192 new/724 total i_, after the
b. Number of assemblies in spent fuel pool: outage 2132 i~

j 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned c, in number of fuel assembiles:

J a. Licensed storage capacity for spent fuel: 2920 l b. Planned increase in IIcensed storage: 4636 new/7556 total

.J 9 The projected date of the last refueling that can be discharged to the

[7 spent fuel pool assuming the present IIcensed capacity:

f'-

V.

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86

/V F2 P Ft C) \/ EE E)

I i APR 2.01978

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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined malow:

ACAD/ CAM - Atmospheric Containnent Atmospheric Dilution / Containment Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS - Anticipated Transient Uithout Scram BWR -

Boiling Water Reactor CRD -

Control Rod Drive EHC - Electro-Hydraulic Control System EOF -

.ne rgency Operations Facility ,

CS EP -

Gecerating Stations Emergency Plan H EPA - High-Ef ficiency Particulate Filter HPCI - High Pressure Co. lant Injection System HRSS -

High Radiation Sampling Systed ,

IPCLRT - Integrated Primary Containment Leak Rate Test IRM - Intenmediate Range Monitor ISI -

Inservice Inspection ,

LER -

Licensee Event Report LLRT -

Local Leak Rate Test .

LPCI - Low Pressure Coolant Injection Mode of RHRS LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC -

Maximum Permissible Concentration MSIV -

Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCW - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS -

Residual Heat Removal System RPS -

Reactor Protection System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System.

SBLC -

Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM -

Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traveling Incore Probe TSC - Technical Support Center

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